LIQUID METAL FUEL REACTOR EXPERIMENT. LIQUID BISMUTH DYNAMIC CORROSION TESTS

Technical Report · Wed Jun 01 04:00:00 EDT 1960

OSTI ID:4137012

Deville, R E; Foley, W R

To confirm the suitability of Croloy 2 1/4 as a material of construction for the Liquid Metal Fuel Reactor and to investigate Croloy l 1/4 as a possible altennate material, liquid bismuth was pumped through 3/4-in. Sch 40 pipe of these two materials at various temperatures, temperature differentials, and with various additives dissolved in the liquid bismuth. The conclusions of these tests may be summarized as follows. Croloy 2 1/4 and Croloy 1 1/4 are suitable materials of construction, zirconium added to the liquid bismuth inhibits container material corrosion. Corrosion specimens in the loop show that Croloy 1 1/4 is more resistant to corrosion by liquid bismuth than Croloy 2 1/4. Most corrosion attack was in the hot leg and was intergranular. With proper welding techniques, no preferential attack was noted in the weld metal. Surface preparation appears to have no effect on corrosion. Iitial uranium and zirconium concentrations could not be maintained throughout the tests. Precipitation appears to be a function of temperature, so the problem can be eliminated by further work. Cavitationcorrosion effects caused rapid failure in the hot leg. Transported metal was usually found in the cold legs. (auth)

• Research Organization: Babcock and Wilcox Co. Research Center, Alliance, Ohio
• NSA Number: NSA-15-004247
• OSTI ID: 4137012
• Report Number(s): BAW-1253
• Country of Publication: United States
• Language: English

Related Subjects

BISMUTH
BISMUTH ALLOYS
CHROMIUM STEELS
CORROSION
CROLOY
LIQUID METAL FUEL
MATERIALS TESTING
METALS, CERAMICS, AND OTHER MATERIALS
PIPES
PRECIPITATION
REACTORS
TEMPERATURE
URANIUM ALLOYS
WELDING
ZIRCONIUM ALLOYS